US4026675A - Heat exchanger for nuclear reactor installations - Google Patents
Heat exchanger for nuclear reactor installations Download PDFInfo
- Publication number
- US4026675A US4026675A US05/589,436 US58943675A US4026675A US 4026675 A US4026675 A US 4026675A US 58943675 A US58943675 A US 58943675A US 4026675 A US4026675 A US 4026675A
- Authority
- US
- United States
- Prior art keywords
- vessel
- heat exchanger
- liner
- space
- flange
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
- 238000009434 installation Methods 0.000 title description 8
- 238000006243 chemical reaction Methods 0.000 claims abstract description 28
- 239000003054 catalyst Substances 0.000 claims abstract description 8
- 239000012528 membrane Substances 0.000 claims abstract description 7
- 238000012856 packing Methods 0.000 claims abstract description 7
- 239000000463 material Substances 0.000 claims abstract description 4
- 238000007789 sealing Methods 0.000 claims description 13
- 238000002407 reforming Methods 0.000 claims description 5
- 229910000831 Steel Inorganic materials 0.000 abstract description 15
- 239000010959 steel Substances 0.000 abstract description 15
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 4
- 239000007789 gas Substances 0.000 description 36
- 239000011513 prestressed concrete Substances 0.000 description 5
- 239000012530 fluid Substances 0.000 description 4
- 230000003197 catalytic effect Effects 0.000 description 3
- 238000001311 chemical methods and process Methods 0.000 description 3
- 238000010276 construction Methods 0.000 description 3
- 239000002918 waste heat Substances 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 239000012809 cooling fluid Substances 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 2
- 230000008646 thermal stress Effects 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 230000008602 contraction Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012634 fragment Substances 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000012495 reaction gas Substances 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B3/00—Hydrogen; Gaseous mixtures containing hydrogen; Separation of hydrogen from mixtures containing it; Purification of hydrogen
- C01B3/02—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen
- C01B3/32—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air
- C01B3/34—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents
- C01B3/38—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents using catalysts
- C01B3/384—Production of hydrogen or of gaseous mixtures containing a substantial proportion of hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air by reaction of hydrocarbons with gasifying agents using catalysts the catalyst being continuously externally heated
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P20/00—Technologies relating to chemical industry
- Y02P20/10—Process efficiency
- Y02P20/129—Energy recovery, e.g. by cogeneration, H2recovery or pressure recovery turbines
Definitions
- the invention concerns a heat exchanger which is to be installed in a nuclear reactor of the cavern type, the heat exchanger being located in a cavern with an impermeable steel liner, and having a large number of reaction tubes filled with reforming catalyst.
- the material to be subjected to reforming mostly hydrocarbons, flows through this reforming catalyst.
- the reaction tubes are heated by the reactor recycle gas.
- Heat exchangers of the type mentioned utilize the waste heat of a nuclear reactor in order to carry out chemical processes. With such heat exchangers, it is necessary to take into consideration the mode of operation of the catalytic high-temperature reaction and to conform to the safety specifications for installations with high-temperature nuclear reactors.
- the equipment that transfers the waste heat of the nuclear reactor is arranged radially in caverns in the pre-stressed concrete that surrounds the nuclear reactor core.
- the caverns have a steel lining, or liner, that has at least one cover plate above and below.
- Appropriate reaction tubes are arranged in the heat exchanger if the waste heat of the nuclear reactor is to be used for carrying out chemical processes.
- the reaction tubes for the endothermic catalytic high temperature reaction, for example methane reforming are filled with catalyst pellets.
- the gas to be reformed passes downwardly through the reaction tubes and is simultaneously heated with the hot recycle gas in order to maintain the endothermic reaction. Differing film and heat transfer coefficients occur inevitably because of irregularities in the catalyst filling and differing reaction rates and gas velocities.
- the tube is subjected to a varying thermal stress and that, in places, this tube may be overheated and destroyed. Because of the specific high loading of the reaction tube and the quality of the material employed, the tubes cannot all have the same service life and some will become defective before others.
- This invention proposes to solve the problem of designing a heat exchanger for a nuclear unit in such a way that its installation is simple, that it has a high degree of operational safety and reliability, and that the previously described problems do not occur.
- the invention solves this problem in placing the reaction tubes in a double walled vessel in the steel liner with the catalyst-free inlet and outlet pipes of the reaction tubes passing through the vessel covers or bottoms, respectively, either individually or in groups.
- the outlet pipes act as a heat exchanger in the double walled vessel space that is filled with water.
- the double walled vessel rests upon a circular bracket in the lower part of the steel liner, and the annular space between the steel liner and the vessel being doubly sealed by a double flange, the circular cover and the membrane ring above and by the double flange and two circular elements below.
- the annular space is sealed by a packing against the recycle gas nozzle.
- reaction tubes of the heat exchanger are double walled, thus providing a double protection against the hot gases outside.
- the inner wall of the heat exchanger is adequately cooled.
- the water jacket fulfills a double function: on the one hand, the water serves as coolant and on the other, a supplementary element of safety is thereby provided.
- the feedwater is heated on the one hand by cooling the reaction fluid that passes through the outlet pipes in the lower part of the double walled heat exchanger and on the other hand by the recycle gas that flows through the inside of the heat exchanger.
- the FIGURE is a vertical sectional view of a heat exchanger and showing a fragment of a cavern type nuclear reactor.
- a pre-stressed concrete vessel 1 of a nuclear reactor installation has several caverns 2 which are disposed radially and usually symmetrically around the reactor core, and of which only one is shown in the drawing as an example.
- the steel liner 3 of the cavern which is to accommodate the heat exchanger, must be able to be closed tightly for safety reasons. Consequently, the invention provides for a circular bracket 4 forming a part of the steel liner to support the double walled vessel 5 and both ends of the steel liner are equipped with two flanges each, those outside 6 and 6' and those inside 7 and 7'.
- the double walled vessel 5 is formed with an outer wall 8 and an inner wall 9.
- Reaction tubes 10 filled with catalyst are placed vertically within the inner wall 9 of the vessel 5.
- the inlet and outlet pipes 11 and 12 are without catalyst and enter the vessel through the top and bottom, either separately or in a group.
- the spacing between the two lower walls of the vessel 5 is such that the pipes that pass through are able to act as a heat exchanger.
- the intermediate space between the outer and inner walls of the double walled vessel 5 is filled with feedwater and serves as a steam generator.
- the design of these passages for the inlet and outlet pipes through the cover and bottom forms no part of the present invention.
- the hot recylce gas having a temperature in the region of 950° C. from the core of the high temperature nuclear reactor passes into the pre-stressed concrete vessel 1 through a hot gas pipe 13 and a passage 14 of the vessel 5 into the interior of the vessel.
- the hot gas is directed around the reaction tubes 10 by means of a known gas distribution or baffle device 15 and the gas temperature is lowered to about 700° C. by transferring heat to the reaction fluid in the reaction tubes.
- the recycle gas leaves the heat exchanger through a passage 16 of the vessel and flows into another heat exchanger, for example a steam generator, through a cold gas tube 17. In this steam generator, the gas is cooled to 250° C. and returned to the high temperature nuclear reactor where it is heated again.
- the hot gas pipe 13 and the cold gas pipe 17 are not rigidly connected with the corresponding passages 14 and 16.
- a single packing 19 is used in the region of the cold gas pipes. It will be understood that several packings could become necessary depending upon the size of the installation. This packing prevents a gas leak from the hot gas pipe 13 into the cold gas pipe 17, that is to say, it is rated to withstand the difference in pressure between the hot and cold gas.
- This space 18 is filled with gas that cannot escape anywhere, this space acts as thermal insulation for the hot recycle gas stream from the hot gas pipe 13.
- a special sealing between the pipes 16 and 17 is not necessary.
- a packing 19 assures that the expansion and contraction of the double walled vessel 5, caused by the high operating temperature, have no effect on the operational capability.
- the cylindrical part of the double walled vessel 5 may be replaced by a cylindrical membrane wall that is well known in boiler construction.
- a pure gas acting as a sealing gas is introduced into the sealing gas space 25 and 26 in order to ensure that no recycle gas - even if cooled - can escape to the exterior.
- the gas pressure in these areas is calculated so as to be superior to the pressure of the hot gas, so that in case of a possible leakage in the flanges, the pure gas will in any case flow into the annular space 18.
- the vessel may be equipped on the inside with a thermal insulation layer (not shown).
- a thermal insulation layer not shown.
- the amount of steam generated from the feedwater in the double wall of the vessel would be considerably less.
- the two annular elements 23 and 24 can be designed in various manners following the requirements. The only necessity is to guarantee a proper sealing at the prevailing operating temperatures.
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Health & Medical Sciences (AREA)
- General Health & Medical Sciences (AREA)
- Combustion & Propulsion (AREA)
- Inorganic Chemistry (AREA)
- Plasma & Fusion (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Details Of Heat-Exchange And Heat-Transfer (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DT24314781 | 1974-07-01 | ||
DE2431478A DE2431478A1 (de) | 1974-07-01 | 1974-07-01 | Waermetauscher zum einbau in eine atomreaktor-anlage |
Publications (1)
Publication Number | Publication Date |
---|---|
US4026675A true US4026675A (en) | 1977-05-31 |
Family
ID=5919379
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US05/589,436 Expired - Lifetime US4026675A (en) | 1974-07-01 | 1975-06-23 | Heat exchanger for nuclear reactor installations |
Country Status (12)
Country | Link |
---|---|
US (1) | US4026675A (de) |
JP (1) | JPS5128579A (de) |
BE (1) | BE830293A (de) |
BR (1) | BR7504156A (de) |
CA (1) | CA1030670A (de) |
CH (1) | CH591748A5 (de) |
DE (1) | DE2431478A1 (de) |
FR (1) | FR2277416A1 (de) |
GB (1) | GB1512085A (de) |
IT (1) | IT1038956B (de) |
NL (1) | NL7507563A (de) |
SE (1) | SE398936B (de) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4127389A (en) * | 1977-04-04 | 1978-11-28 | Pullman Incorporated | Exchanger reactor |
US4221262A (en) * | 1976-11-06 | 1980-09-09 | Hochtemperatur-Reaktorbau Gmbh. | Heat exchanger for the transmission of heat produced in a high temperature reactor to an intermediate circuit gas |
US5429186A (en) * | 1992-08-05 | 1995-07-04 | Forbach Gmbh | Open hot-water heater |
US5695007A (en) * | 1993-03-17 | 1997-12-09 | Faudat Concept | Heat exchanger device and method for cooling the inner chamber thereof |
US20100303192A1 (en) * | 2007-05-07 | 2010-12-02 | Energies, Large & Alternative S.R.L. | Supersafe and simply- / easily-decommissionable nuclear power plant |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112589347B (zh) * | 2020-12-03 | 2023-03-07 | 中国核工业二四建设有限公司 | 一种应用于核电站钢衬里模块整体拼装的调整工装及*** |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3126322A (en) * | 1964-03-24 | Fractionation | ||
US3144312A (en) * | 1961-06-06 | 1964-08-11 | Mertens Carl | Catalytic conversion plant for the continuous generation of gases of any kind out of ydrocarbons |
US3274978A (en) * | 1964-02-24 | 1966-09-27 | Lummus Co | Vertical tube fluid heater |
US3541729A (en) * | 1968-05-09 | 1970-11-24 | Gen Electric | Compact reactor-boiler combination |
US3751228A (en) * | 1970-12-16 | 1973-08-07 | V Semenov | Apparatus for reforming hydrocarbons under pressure |
-
1974
- 1974-07-01 DE DE2431478A patent/DE2431478A1/de not_active Withdrawn
-
1975
- 1975-06-11 IT IT24278/75A patent/IT1038956B/it active
- 1975-06-16 BE BE157375A patent/BE830293A/xx unknown
- 1975-06-18 SE SE7507020A patent/SE398936B/xx unknown
- 1975-06-23 US US05/589,436 patent/US4026675A/en not_active Expired - Lifetime
- 1975-06-25 NL NL7507563A patent/NL7507563A/xx not_active Application Discontinuation
- 1975-06-27 GB GB27326/75A patent/GB1512085A/en not_active Expired
- 1975-06-30 CA CA230,469A patent/CA1030670A/en not_active Expired
- 1975-06-30 CH CH847875A patent/CH591748A5/xx not_active IP Right Cessation
- 1975-07-01 BR BR5315/75D patent/BR7504156A/pt unknown
- 1975-07-01 JP JP50080558A patent/JPS5128579A/ja active Pending
- 1975-07-01 FR FR7520601A patent/FR2277416A1/fr active Granted
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3126322A (en) * | 1964-03-24 | Fractionation | ||
US3144312A (en) * | 1961-06-06 | 1964-08-11 | Mertens Carl | Catalytic conversion plant for the continuous generation of gases of any kind out of ydrocarbons |
US3274978A (en) * | 1964-02-24 | 1966-09-27 | Lummus Co | Vertical tube fluid heater |
US3541729A (en) * | 1968-05-09 | 1970-11-24 | Gen Electric | Compact reactor-boiler combination |
US3751228A (en) * | 1970-12-16 | 1973-08-07 | V Semenov | Apparatus for reforming hydrocarbons under pressure |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4221262A (en) * | 1976-11-06 | 1980-09-09 | Hochtemperatur-Reaktorbau Gmbh. | Heat exchanger for the transmission of heat produced in a high temperature reactor to an intermediate circuit gas |
US4127389A (en) * | 1977-04-04 | 1978-11-28 | Pullman Incorporated | Exchanger reactor |
US5429186A (en) * | 1992-08-05 | 1995-07-04 | Forbach Gmbh | Open hot-water heater |
US5695007A (en) * | 1993-03-17 | 1997-12-09 | Faudat Concept | Heat exchanger device and method for cooling the inner chamber thereof |
US20100303192A1 (en) * | 2007-05-07 | 2010-12-02 | Energies, Large & Alternative S.R.L. | Supersafe and simply- / easily-decommissionable nuclear power plant |
US8660232B2 (en) * | 2007-05-07 | 2014-02-25 | Sergio D'Offizi | Supersafe and simply-/easily-decommissionable nuclear power plant |
Also Published As
Publication number | Publication date |
---|---|
DE2431478A1 (de) | 1976-01-22 |
BE830293A (fr) | 1975-10-16 |
JPS5128579A (de) | 1976-03-10 |
SE7507020L (sv) | 1976-01-02 |
FR2277416A1 (fr) | 1976-01-30 |
NL7507563A (nl) | 1976-01-05 |
CA1030670A (en) | 1978-05-02 |
GB1512085A (en) | 1978-05-24 |
IT1038956B (it) | 1979-11-30 |
SE398936B (sv) | 1978-01-23 |
BR7504156A (pt) | 1976-06-29 |
CH591748A5 (de) | 1977-09-30 |
FR2277416B3 (de) | 1979-02-23 |
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